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MONTHYEARML20195E5231984-09-19019 September 1984 Notifies of 840926 Meeting W/Util in Bethesda,Md to Discuss Generic Ltr 84-08 Issues.Agenda Provided Project stage: Meeting ML20093K5931984-10-12012 October 1984 Forwards Responses to Draft SER Issues 46 & 74 Re Loose Parts Monitoring Sys & Primary Component Cooling Water Isolation from Reactor Coolant Pump Thermal Barriers, Respectively Project stage: Request ML20101F7361984-11-0606 November 1984 Application for Withholding Study Re ESF Actuation Sys Setpoint Methodology (Ref 10CFR2.790) Project stage: Request ML20099G5331984-11-20020 November 1984 Forwards Positions on Backfit Requirements.Further Clarification & Justification to Facilitate Meaningful Appeal Meetings for Evaluating Postulated Increase in Plant Safety Requested Project stage: Request ML20112G8191985-03-27027 March 1985 Forwards Revised Power Sys Branch Mechanical Responses Previously Submitted Informally & Discussed in 850325 Telcon.Fsar Changes Will Be Incorporated in Upcoming Amend. Discussion of Lighting & Communication Included Project stage: Request ML20126M3041985-07-11011 July 1985 Forwards Decision on Appeal of Requirements on Fire Suppression in Cable Spreading Room.Implementation of Certain Human Factor Recommendations Requested Project stage: Other ML20151N8801985-12-24024 December 1985 Forwards Comments on SER (NUREG-1057).Sys Will Be Implemented to Track Resolution of Comments & Future SER Changes.Statement on Page 2-46 Re Susceptibility of Soils Around Intake to Liquefaction Should Be Expanded Project stage: Other ML20207L5331987-01-0606 January 1987 Forwards Updated FSAR Fire Protection Matl in Preparation for Upcoming NRC Fire Protection Audit.Submittal Contains Info for Resolution of SER Open Item 5 & Confirmatory Item 48c.Matl Will Be Incorporated Into Amend 14 to FSAR Project stage: Other ML20207N1901987-01-0808 January 1987 Notification of 870129 Meeting W/Util in Shippingport,Pa to Conclude 4-day Site Review of Fire Protection Issues.Issues Identified as Confirmatory Issue 48 & Backfit Issue 7 in Sser 3 Project stage: Meeting ML20213A5671987-01-27027 January 1987 Requests Security Passes Be Provided to Personnel for 4-day Site Review to Begin on 870108 Re Fire Protection Issues Project stage: Other ML20209G4371987-01-28028 January 1987 Forwards Addl Info Re SER Backfit Item 7 (Fire Suppression in Cable Spreading Room),Per NRC Request in SER Section 9.5.1.6.Response to Item 4 Provided in Jj Carey , Per Sser 3 Project stage: Other ML20155H2511987-02-0505 February 1987 Summary of 870130 Meeting W/Util & S&W in Bethesda, MD to Conclude NRC Fire Protection Site Review of 870127-29.List of Attendees Encl Project stage: Meeting 1985-03-27
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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999 Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System ML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195H4651999-06-16016 June 1999 Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail ML20195J5221999-06-16016 June 1999 Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999 Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109 L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999 Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys L-99-099, Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr1999-06-14014 June 1999 Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr ML20195H3731999-06-0303 June 1999 Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999 Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999 Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1 L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999 Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b) L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999 Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon L-99-082, Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS1999-05-17017 May 1999 Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999 Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS 1999-09-03
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20059E0601990-08-0707 August 1990 Requests That Proprietary Suppl 3 to WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, Be Withheld Per 10CFR2.790(b)(4) ML18094B4141990-03-27027 March 1990 Outlines Plan & Basis for Plan to Update Steam Generator Tube Fatigue Evaluations Performed by Westinghouse in Response to NRC Bulletin 88-002 ML20246H2601989-08-28028 August 1989 Requests That Suppl 2 to WCAP-12093, Addl Info in Support of Evaluation of Thermal Stratification for Beaver Valley Unit 2 Pressurizer Surge Line, Be Withheld from Public Disclosure Per 10CFR2.790 ML20248E8731989-03-0101 March 1989 Application for Withholding Proprietary WCAP-12141, Beaver Valley Unit 2 Evaluation for Tube Vibration Induced Fatigue (Ref 10CFR2.790) ML20245H6201989-02-20020 February 1989 Requests Withholding of Proprietary Suppl 1 to WCAP-12093, Addl Info in Support of Evaluation of Thermal Stratification for Beaver Valley Unit 2 Pressurizer Surge Line, (Ref 10CFR2.790) ML20245G6811988-12-22022 December 1988 Requests That WCAP-12058, Resistance Temp Detector Bypass Elimination Licensing Rept for Beaver Valley Unit 1, Be Withheld (Ref 10CFR2.790) ML20151G3491988-06-16016 June 1988 Requests Withholding of Proprietary Suppl 7,Rev 0 to WCAP-10170, Westinghouse SPDS Design & Verification... Process for Beaver Valley Unit 1 Nuclear Station, from Public Disclosure (Ref 10CFR2.790) ML20154A6511988-04-13013 April 1988 Requests Proprietary WCAP-11799, Beaver Valley Unit 1 Evaluation for Tube Vibration Induced Fatigue, Be Withheld Per 10CFR2.790(b)(4) ML20236S0731987-11-0606 November 1987 Requests That Proprietary Suppl 2 to WCAP-11317, Verification of Fracture Mechanics Analysis Techniques Used in Support of Technical Justification for Eliminating Large Primary Loop Pipe Rupture..., Be Withheld Per 10CFR2.790 ML20236A9631987-10-26026 October 1987 Requests That Proprietary WCAP-11419, Westinghouse Setpoint Methodology for Protection Sys Beaver Valley Unit 1, Be Withheld,Per 10CFR2.790(b)(4) ML20235J4491987-09-18018 September 1987 Requests That Proprietary WCAP-11317,Suppl 1, Addl Info in Support of Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Bases... Be Withheld from Public Discloser Per 10CFR2.790 ML20237L3031987-07-0707 July 1987 Requests That Proprietary WCAP-11522, Response to NRC Question on LOCA Hydraulic Forces Analysis of Beaver Valley Power Station Unit 2, Be Withheld (Ref 10CFR2.790). Affidavit for Withholding Rept Encl ML20206E4521987-03-24024 March 1987 Requests Withholding of Proprietary Addl Info on Beaver Valley Power Station Unit 2 SER Confirmatory Issue 032, from Public Disclosure (Ref 10CFR2.790) ML20209B2041987-01-0909 January 1987 Requests Withholding of WCAP-11366, Westinghouse Setpoint for Protection Sys,Beaver Valley Unit 2, Per 10CFR2.790. Affidavit Encl ML20198J5121986-05-0606 May 1986 Forwards Nonproprietary & Proprietary Addl Info on SER Confirmatory Item 32 Re Analysis of Feedwater Malfunction Event.Affidavit Also Encl.Proprietary Info Withheld (Ref 10CFR2.790) ML20151Z3281986-01-28028 January 1986 Forwards Proprietary Affidavit AW-77-18 Re Withholding Proprietary WCAP-11061, Unit 1 & Unit 2 Differences Analyses,Accident Analyses Per 10CFR2.790.Affidavit Withheld NRC-85-3041, Requests That WCAP-9735, Multiflex 3.0 - Fortran IV Computer Program for Analyzing Thermal-Hydraulic-Structural Sys Dynamics (III) Advanced Beam Model, Be Expeditiously Reviewed & Approved1985-06-18018 June 1985 Requests That WCAP-9735, Multiflex 3.0 - Fortran IV Computer Program for Analyzing Thermal-Hydraulic-Structural Sys Dynamics (III) Advanced Beam Model, Be Expeditiously Reviewed & Approved ML20100E1051985-03-20020 March 1985 Requests That Proprietary Seismic Response Spectrum at Reactor Vessel Supports Be Withheld (Ref 10CFR2.790) ML20107G1131984-12-27027 December 1984 Requests Withholding of Proprietary Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Beaver Valley Unit 1, (Ref 10CFR2.790) ML20140D5721984-12-0404 December 1984 Requests Proprietary Rev 1 to WCAP-9736, Multiflex 3.0, FORTRAN-IV Computer Program for Analyzing Thermal-Hydraulic- Structural Sys Dynamics (III) Advanced Beam Model Be Withheld (Ref 10CFR2.790).Affidavit Encl ML20101F7361984-11-0606 November 1984 Application for Withholding Study Re ESF Actuation Sys Setpoint Methodology (Ref 10CFR2.790) ML20098C8591984-08-14014 August 1984 Alleges That Unqualified Suppliers Awarded Contracts from Plants to Provide Flexible Conduits Unqualified Under IEEE Stds 323 & 344 Despite IEEE Bid Requirements.Meeting Re NRC Position on safety-related Installations Requested ML20093G8991984-06-0606 June 1984 Requests That WCAP 10565, Technical Bases for Eliminating Large Primary Loop Rupture as Structural Design Basis for Beaver Valley Unit 2, Be Withheld from Public Disclosure, Per 10CFR2.790 ML20083P7631984-03-0909 March 1984 Requests Withholding WCAP-10493, Third Cycle Performance of Beaver Valley Unit 1 Fuel, from Public Disclosure,Per 10CFR2.790.Authorizes Use of Affidavit AW-76-35 in Support of Util Request ML20082P8901983-11-10010 November 1983 Application for Withholding Proprietary Steam Line Break Blowdown Data (Ref 10CFR2.790).Affidavit Encl ML20074A0151983-04-20020 April 1983 Application for Withholding Proprietary WCAP-10196, Second Cycle Performance of Beaver Valley Unit 1 Fuel, Per 10CFR2.790.Affidavit Encl ML20028C7361982-12-31031 December 1982 Forwards Proprietary & Nonproprietary Incore Detector Thimble Reduction Study, Submitted in Support of 821216 Proposed Tech Spec Change Request 75.Proprietary Rept Withheld (Ref 10CFR2.790).Affidavit Encl ML20008G1421981-06-11011 June 1981 Advises That Facility Should Be Deleted from 810610 Part 21 Rept Re Missile Penetration Analysis ML19350C9491981-04-0808 April 1981 Authorizes Use of Encl Previously Furnished Affidavit for Withholding Portion of Cycle 2 Rod Misalignment Analysis (Ref 10CFR2.790) ML19347D4311981-01-21021 January 1981 Forwards Affidavit Requesting That Analytical Results of Impact of Increased Rod Misalignment on Peaking Factors Be Withheld (Ref 10CFR2.790) ML19347C7401980-12-23023 December 1980 Requests That Proprietary Info Submitted as Responses to NUREG-0737 Re Instrumentation for Inadequate Core Cooling Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl ML19249E8941979-09-19019 September 1979 Notifies of Failure of Personnel Fabricating Pipe Spools to Comply W/Asme Boiler & Pressure Vessel Code Re Welding Qualifications.Work Ceased Upon Issuance of Rept by Inspectors ML19289E6271979-03-23023 March 1979 in Response to 780922 Part 21 Rept,Informs That Injection Pumps Were Removed & Inspected Using Newly Established Criteria of Suppl 2, & Were Reinstalled on Engines.No Further Action Contemplated ML19289E6241979-03-22022 March 1979 Notification of Test Results Indicated in 780922 Part 21 Rept.Cites Three Causes of Injection Pump Failure.Concludes Pumps Are Now Adequate.No Further Action Contemplated ML19263D6021979-03-22022 March 1979 Notifies NRC Insp Completed Re Exhaust Rocker Arms of Two PC-2 Generator Sets.Unit Free of Potential Defects ML20083P7681976-08-13013 August 1976 Requests Withholding Info,Re Notification of Generic Problems Under 10CFR50.59(a) & 10CFR50.55(e) on Increased Temp in Upper Head & DNB Penalty Re Rod Bow,From Public Disclosure,Per 10CFR2.790.Affidavit Encl 1990-08-07
[Table view] |
Text
, .. .. .
s- m
[ Enclo:ure 5
\ /
sJ Nuclear Technology D;nsion Westinghouse Water Reactor Electric Corporation Divisions Box 335 PittsburghPennsylvanta 15230 November 6,1984 Mr. George W. Knighton, Chief CAW-84-97
. Licensing Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE SUB.1ECT: Westinghouse Input to Beaver Valley Power Station Unit 2 Setpoint Study REF: Duquesne Light Company Letter, Woolever to Knighton, dated November 1984
Dear Mr. Knighton:
The proprietary material for which withholding is being requested is of the same technical type as that proprietary material previously submitted by Westinghouse concerning reactor Protection System / Engineered Safety Features Actuation System Setpoint Methodology. The previous application for withholding, AW-76-60, was accompanied by an affidavit signed by the owner of the proprietary information, Westinghouse Electric Corporation.
Further, the affidavit submitted to justify the previous material was approved by the Commission on April 17, 1978, and is equally applicable to the subject taterial.
Accordingly, it is respectfully requested that the subject information which is proprietary to Westinghouse and which is further identified in the affidavit be withheld from public disclosure in accordance with 10CFR Section 2.790 of the Consnission's regulations.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference CAW-84-97 and should be addressed to the undersigned.
B Very truly yours,
{jj22702k6$og&p ADOC o ~
PDR p y )
/Isb 86be A. Wiesemann, Manager -
p
- Reg atory & Legislative Affairs Attachment cc: E. C. Shomaker, Esq.
Office of the Executive Legal Director, NRC
i
- Enclosure No. 2 i TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOIITTS FUNCTIONAL UNIT TRIP SETPOINT ALIDWABLE VAIRES
- 1. Manual Reactor Trip Not Applicable Not' Applicable
- 2. Power Range, Neutron Flux Iow Setpoint - < 25% of RAT ED Iow Setpoint - < 26% of RAT ED THERMAL POWER THERMAL POWER l
High Setpoint - < 109% of RATED High Setpoint - < 110% of RATED THERMAL POWER TH ERMAL POWER -
- 3. Power Range, Neutron Flux, High < 5% of RAT ED ThlERMAL POWER with < 5.5% of RATED THERMAL POWER with Positive Rate a time constant > 2 second a t ime cons t ant > 2 second
- 4. Power Range, Neutron Flux, High < 5% of RATED THERMAL POWER with < 5.5% of RAT ED THERMAL POWER with Cegative Rate a time constant > 2 second a t ime cons t ant > 2 second
- 5. Intermediate Range, Neutron Flux < 25% of RATED THERMAL POWER < 30% of RATID THERMAL POWER
- 6. Source Range, Neutron Flux < 105 counts per seconc < l.3 x 105 counts per second
- 7. Overtemperature Delta T See Note 1 See Note 2
- 8. Overpower Delta T See Note 3 See Note 4
- 9. Pressur izer Pressure--Low > 1945 psig > 1935 psig
- 10. Pressurizer Pressure--High < 2385 psig < 2395 psig
- 11. Pressur izer Water Iavel--High < 92% of instrument span < 93% of instrument span
- 12. Loss of Flow > 92% of design flow per loop * > 91% of design flow per loop *
- Design flow is 88,500 gym per loop. .
CEAVER VALLEY UNIT 2
. Enclosure No; 2--.
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTDI INSTRUMBITATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALIDWABLE VAIRES
- 13. Steam Generator Water Level--Iow-Low > 14.2% of narrow range instrument > 13.2% of narrow range instrument span-each steam generator span-each steam generator
- 14. Steam /Feedwater Flow Mismatch and Iow ~< 40% of full steam flow at RATED THERMAL < 42.5% of full steam flow at . RATED Steam Generator Water 'Invel POWER coincident with stean generator THERMAL POWER coincident with steam .
water level generator water level
> 25% of narrow range instrument span-- > 24% of narrow range instrument each steam generator span--each stems ' ge nerator
- 15. Undervoltage-Reactor Coolant Pumps 75% _+If of nominal bus voltage- > 70% of nominal bus voltage-each eachhus Tus -
- 16. Under frequency-Reactor Coolant Pumps > 58.0 H, -each bus > 57.5 H, -each bus
- 17. Turbine Trip
- a. Auto Stop Oil Pressure 45 psig + 5 psig-l l b. Turbine Stop Valve > 1% open > 1% open
- 18. Safety Injection Input from ESF Not Applicable Not Applicable 1
- 19. Reactor Coolant Pump Breaker Not Applicable Not Applicable Position Trip BEAVER VALLEY UNIT 2 '2-7
c -
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS -l NOTATION NOTE 1: OVERTEMPERATURE Delta T (1 + tgS) 1 (1 + t 4)
S 1 Delta T ( ) < Delta To K1-K2 .
[T ( )- TI ] + K3 - (P - PI ) - fh -(Delta I)
(1 + t 2)
S I + C3S (I + t SS) 1 + e68
~
Where: Delta T = Measured Delta T by RTD Manifold Instrumentation;-
l+tS 1
= Lead-lag compensator on measured Delta T; I + t2S ti, t2 = Time constants utilized in lead-lag controller for Delta T, t1 = 8 seconds, t2 = 3 seconds; 1
= Lag compensator on measured Delta T; I+tS 3 t3 = Time constants utilized in the lag compensator for Delta T, t3 = 0 seconds; Delta To = Indicated Delta T at RATED THERMAL POWER;
= 1.2261 for 3 loop operation Kg K2
= 0.01747; BEAVER VALLEY UNIT 2 2-9
i ,
Enclosure:
No.'2'
! TABLE 2.2-1 1 (Cont inued) l
. REACTOR TRI_P SYSTEM INSrRUMENTATION TRIP SETPOINTS ~
NOTATION (Cont inued)
Nor E 1: (Continued) i 1 + t4S
= The function generated by the lead-lag controller for T - dynamic compe ns at ion; .
'* 8 1 + tSS t4, t5 =
Time constants utilized in the lead-lag controller for T ,,8, t4 = 30 seconds , . t5 "
4 seconds; T = Average temperature. *F;
=
1 Lag compensator on measured T,y ;
1 + t6S t6 =
Time constant utilized in the measured T,y lag compensator, t6 = 0 seconds; ,
TI -
< -576.2*F (Nominal T avg at RKT ED THERMAL POWER);
K3
= 0.000823; P = Pressurizer pressure, psig; PI = 2235 psig (Nominal RCS operating pressure); and,
~
BEAVER VALLEY UNIT 2
Enclosure No; 2' TABLE 2.2-1 (Cont inued)
REACTOR TRIP SYSTEM INSTRUMENT _ATION TRIP SETPOINTS NOTATION (Cont inued)
NOTE 1: (Continued)
S = Laplace trans form operator, second-l; and f3 (Delta I) is a function of the -indicated difference between top and bottom detectors of the power-range-nucle ar ion chambers; with gains to be selected based on measured instrument response during plant startup tests such that:
(i) For at ' 9 between -34% and + 10% f -(Delta I) = 0, where q and q 8re Percent RAT ED THERMAL' POWER
~
b i b
in the top and bottom halves of the core respectively, and q + qb ts total THERMAL POWER in percent:
of RATED THERMAL POWER; (ii) For each percent that the magnitude of q qb exceeds -34% the Delta T Trip Setpoint shall be' automatically reduced by 1.439% of its value at RATED THERMAL POWER; and (iii) For each percent that the magnitude of q exceeds +10% the Delta T Trip Setpoint shall be automatically reduced by 1.789% of its value at t ~9b RAT ED THERMAL POWER.
NOTE 2: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 3.8%.
BEAVER VALLEY UNIT 2 2
- ,5 _ 5-.. .
_g . . ; :, y; =;;: ,;; ' :::. _
~~ w V
. , Enclosure No. '2 TABLE 2.2 (Cont inued) . ,.
REACTOR TRIP SYSTEM INSTRUMBtr_ATION TRIP _SErPOIlfrS '
- N0 RATION (Cont inued)
NOT E 3: OVERPOWER De1ta T 1 + tgS I t7S 1 1 Delta T ( )( )< Delta To
~
K4~K5( )( )T-K6 [T ( ~ )-Til] - f2 (Delta T)
-1 + t2S l + C3S 1+t7S 1 +"t68 l' + C68 Where: Delta T = As defined in Note 1; I + tgS
= As defined .in Note 1; I+t28
= As defined in Note 1; -
tt, t2 1
= - As defined in Note 'l; I + t3S t3 = As de[ined in Note 1;
= As defined in Note 1; Delta TO K4
= 1.0851 2~
BEAVER VALLEY UNIT 2 ,
. Enclosure'Ns.l2
. TABLE 2.2-1 (Cont inued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP _ SETPOINTS NOTAT ION (Cont inued)
NOT E 3: (cont inued)
K5
=
0.02/*F for increasing average ' temperature and 0 for decreasing average temperature; t7S
=
The function generated by the rate-lag controller. for T, ' dynamic compensation; t7 =
Time constants utilized in the rate-lag controller for T,yg, t7 = 10 seconds; 1
= As defined in Note 1; I + t6S
=
t6 As defined in Note I; K6
=
0.00ll5/*F for T > TIl and K6 = 0 for T < TII; T = As defined in Note 1; Til = As indicated T at RATED THERMAL POWER (Calibration temperature for Delta T instrumentat io$"8< 576.2*F);
2-13 BEAVER VALLEY UNIT 2
r < - -
3
,1 ,
. . Enclosure No. 2 ,
TABLE 2.2-I~
(Cont inued) .
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP - SETPOIlff S NOTATION
- (Cont inued)
NOTE 3: (Continued) i S = As defined in Note 1; and f2 (Delta I) = 0 for all I a
~
NOT E 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by.more than 3.0%.
BEAVER VALLEY UNIT 2 2-14
3
' TABLE.3.3-4 ENGINEERED SAFETY FEATURE' ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS Functional Unit Trip Setpoint -Allowable Values
- 1. SAFETY INJECTION AND FEEDWATER ISOLATION
- a. Manual Initiation Not Applicable LNot Applicable
- b. Automatic Actuation Logic Not Applicable Not Applicable:
- e. Containment Pressure - High f 1.5 psig i 2.0.psig d.-Pressurizer Pressure - Low 1 1,875 psig > 1,866 psig
- e. Steam Line Pressure - Low > 525 psig >'510 psig-steam line pressure- steam line pressure 1.1 SAFETY INJECTION - TRANSFER FROM INJECTION TO THE RECIRCULATION MODE
- a. Automatic Actuation Logie Coincident with Not Applicable Not Applicable Safety Injection Signal
- b. Refueling Water Storage Tank Level - Low 37'2" '37'2" + 1.9" BEAVER VALLEY UNIT 2 3/4 3-23
~..- -
Enclosure No.'2 TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINT S Functional Unit Trip Setpoint Allowable Values
- 2. CONTAINMENT SPRAY
- c. Manual Initiat ion Not Applicable -- Not Applicable
- b. Automatic Actuation Logic Not Applicable ' Not Applicable
- c. Containment. Pressure - High-High i8.0psig .I 8.8 psig i
3, CONTAINMENT ISOLAT ION
- a. Phase "A" Isolation
- 1) Manual Not Applicable - Not Applicable-
- 2) From Safety Injection Automatic Not Applicable Not Applicable Actuation Logic
- b. Phase "B" Isolation
- 1) Manual Not Applicable _ Not Applicable
- 2) Automatic Actuation Logic Not Appliceble Not Applicable Actuation Logic
- 3) Containment Pressure - High High i 8.0 psig i 8.8'psig BEAVER VALLEY UNIT 2 3/4 3
-Enclosure No.'2 TABLE 3.3-4 (Continued)
ENGIN EERED SAFETY FEATURE ACrUATION SYSTEM INSrRUMENTATION TRIP SETPOINT S Functional Unit Trip Setpoint Allowable Values
- 4. Sr EAM LINE ISOLATION
- a. Manual Not Applicable Not' Applicable L _
- b. Automatic Actuation Log .ci Not Applicable ' Not Applicable L
- c. Containment Pressure - Intermediate High High < 3.0 psig -< 3.8.psig
-d. Steam Line Pressure - Low > 525 psig > 510 psig steam line pressure steam line . pressure
- e. High Steam Pressure Rate -100 psi -110 psi
- 5. TURBINE TRIP AND FEEDWATER ISOLATION
- a. Steam Generator Water' Level - High-High < 75% of narrow range < 76% of- narrow range Ins tr ume nt span each Ins trume nt span each stean generator stema generator BEAVER VALLEY UNIT 2 3/4 3-25
cl Enclosura Ns. 2' '
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMDITATION TRIP SETPO_ INT S
- Functional Unit '
Tr ip Setpoint - Allowable Values
- 6. LOSS OF : POWER
- a. 1) 4.16kv Bnergency Bus Undervoltage 75% !jf of nominal' bus > 70% of nominal bus (Loss of Voltage) (Trip Feed) voltage with a 1 + 0.1 voltage with a 1 + 0.1 second time delay second time delay
- 2) 4.16kv Bnergency' Bus ( Start Diesel) 75%1If > 70% of nominal bus volta $e,of 20nominal cycles +bus 2 cycles voltage, 20. cycles + 2 cycles
- b. 4.16kv Emergency Bus Undervoltage 90% [ff of nomiani bus > 89% of nominal bus (Degr aded Voltage) voltage with a 90 1 5 voltage with a 90 + 5 second time delay second time delay
- c. 480v Emergency dus Undervoltage 90% 1}f of nominal bus > 89% of nominal bus (Degr aded Voltage) voltage with a 90 ~+ 5 . voltage with a 90 + 5 -
second time delay second time delay BEAVER VALLEY UNIT 2 3/4 3-26
g- ,
, -y - -
. q..
3 r
.. Enclosure No. 2-TABLE 3.3-4 (Continued) .
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMBrrATION <
. TRI_P SETPOINT S ,
Functional Unit Trip Setpoint IAllowable Values
- 7. AUXILIARY FEEDWATER
- a. Steam Generator Water Level - Low-Low > l4'j2%of narrow range >l3.2%of, narrow' range Ins tr ument span each Ins tr ume nt span each steam generator . steam generator
- b. Undervoltage - RCP 75% !ff of ' nominal bus.. > 70% of nominal. RCP bus voltage voltage
- c. S. I. See 1 ab ove ' ( al l S. I. .. Setpoints ) -
- d. Turbine-Driven Auxiliary Feed Pump Disch pressure > 150 psig Disch pressure > 140 psig Discharge Pressure Low with Steam with stean inlet valves open with stean -. inlet . valves open Valves Open
- e. Te ip of Main Feedwater Pumps Not Applicable Not Applicable
- f. Snergency Bus Undervoltage 75% ll of nominal bus > 70% of nominal bus voltage voltage
- 8. ESF INTERLOCKS
- a. P-4 N/A' N/A
- b. P-ll . < 2000 psig < 2010 psig
- c. P-12 .(later), .(later)
BEAVER VALLEY UNIT 2 3/4 3-27
g -. ,
/
ENCLOSURE 1 JNRC. Draft SER Information' Request Section 7.2.2.4: -Trip Setpoints and. Margins-The _ staf f ' requested detailed information on the methodology used to estab--
-lish the Technical- Specification (TS) trip setpoints and allowable values for. the reactor protection system _(RPS) . (including reactor trip and engi-
~
neered - - s afe ty > fe ature channels) assumed to operate in the FSAR ' accident -
and transient analyses. This includes'the following information:
-(1) The. trip setpoint and allowable value for the TS.
(2) The safety -limits necessary. to protect the integrity .of the physical-barriers which guard against. uncontrolled release of radioactivity.
t (3) The . values ~ assign'ed to .' each ~ component of the combined ch annel error s allowance f. e . g . , modeling uncertainties, analytical' uncertainties, transient overshoot , . response time, trip unit setting accuracy, , test
. equipment accuracy, primary element accuracy, sensor drif t, nominal Land harsh environmental allowances, trip unit drift), the basis for these. values, and the method used to sum the individual errors. W ere zero:is assumed: for an error, a justification that the error is .negli-gible.should be provided.
(4)'The margin (i.e., the ~ dif ference between the safety limit and the setpoint-less the combined channel error allowance). *
~~
Response
'.(1) The recommended Nominal- Trip . Setpoints and the Allowable Values fo r .
the TS are as identified on Enclosure 2. Enclosure 2 is a :reproduc .
. t ion ~of Table . 2.2-1 for the RPS -trips and of Table 3.3-4 for the ESF actuations ' from the draf t Beaver Valley Power Station Unit 2 (BVPS-2)
TS.
- (2) For those trips assumed to function in the accident analyses, the Safety Analysis Limit is as identified on Enclosures 3 and _4. ' Trips not assumed to function in any safety analyses are identified as "Not Used."
._ (3) The- values assigned to individual uncertainty components are as ide n-tified on Enclosures 3 and 4. The uncertainties are broken down into s component uncertainties using the standard Westinghouse nomenclature, which isidefined below:
-(a) Process Measurement Accuracy (PMA)
P Includes plant variable me'asurement errors up to but not including the sensor. Examples are the effect of fluid stratification on temperature measurements and the ef feet of changing fluid density on . level measurements. An' inaccuracy due to a non-ins trument effect.
-(b) Primary Element Accuracy (PEA),
This ' accuracy is defined as the accuracy exhibited by the primary
' element in the measurement of a process parameter. Used for ventures (flow), orifices, or elbow elements and accounts for noise.
(c) Sensor Allowable Deviation The - accuracy that can be expected in the field. It includes drift, temperature of fects, field calibration and, for the case of d/p transmitters, an allowance for the ef fect of static pressure variations. Sensor is interchangeable with transmitter.
The tolerances are as follows:
- 1) Reference (calibration) accuracy (SCA): This accuracy is the-SAMA reference accuracy as de fined in SAMA standard PMC-20 1973 2,
- 2) Temperature ef fect (STE): Base on nominal temperature coef fi-cient and a maximum assumed charge of 50*F.
- 3) Pressure effect (SPE): Usually calibrated out because pressure is constant. If not constant, a nominal value is used.
- 4) Drift (SD): Change in input-output relationship over a period of time at reference conditions.
(d) Environmental Allowance (EA)
This allowance is defined as the maximum channel ' deviation that is expected to occur solely due .to the ef fects of being exposed to a high energy line break environment. The ef fects of a high energy live break environment include temperature, pres sur e , humidity, radiation , chemical spray, acceleration, and vibration. This ,
error also includes allowances, whe re applicable, for reference leg heatup on level delta P sensors.
(e) Rack Allowable Deviation The. tolerances are as follows:
- 1) Rack . calibration accuracy (RCA): The accuracy that can be expected during a calibration at reference conditions. This accuracy is the SAMA reference accuracy as ' defined in SAMA standard PMC-20-1-19732 This includes all nodules in a rack.
For simple loops where a power supply (not used as a converter) is the only rack module, this accuracy may be ignored.
- 2) Rack environmental ef fects (RTE): Includes effects of tr.mpera-ture, humidity, volt age , and frequency ch ange s , of which temperature is the most significant.
.a, . . -- . , . - , -. - -- _. . . - - . . _ . . - . -
- 3) Comparator setting accuracy (RCSA): Assuming an exact elec-tronic input, note that the "channel accuracy" takes care of deviations from this ide al), the tolerance on the precision with which a comparator trip value can be set, within such practical constraints as time and ef fort expended in making the setting. RCSA is interchangeable with trip unit setting accuracy.
~The tolerances consider the following:
a) Fixed: setpoint with a single input: This assumes that comparator nonlinearities are compensated by the setpoint.
+
b) Dual input: An additional error must be added for compara-tor nonlinearities between two inputs.
- 4) Rack drif t- (instrument channel drif t) (RD): Change in . input-output relationship . over a period of time at reference conditions.
' The method used by Duquesne Light Company to calculate the trip.
setpoint meets the intent of References 1, 2 , and 3. The method-ology is as summarized below:
Safety Limit (Referen'ec 1)
A Allowable Value TS Reportable Occurrence Upper Setpoint Readjustment Limit Required Trip Setpoint No Readjusting Necessary Lower Setpoint Readj us tment Limit h Required Upper Band of Normal Operation Plant Availability Normal Operation T (' p- p 4 v - - + - me -.m-e--,um . e--g ,r >ymen > g y--y .g. w g -ip.,* - -we-- --- g -- ---
Comp _utation of Instrume_nt, Inaccuracies (II)*
11 = PMA + E A + l [PE A2 + SCA2 + SPE2 + STE2 .+ SD2 + RCA2 + RCSA2#
RTE 2'+'RD 2 ]1/2,*
. Computation of Nominal' Safety System Setting (hereaf ter refered to as
-Trip.Setpoint)
Trip Setpoint = Safety Limit.+. (II and Margin) x Span Where Trip. Setpoint = The ' desired setpoint for the vari ab le .
Initial c alibration . and subsequent. calibrations should reset the trip setpoint to this value.
Safety Limit ' = The trip setpoint value assumed in safety analyses (S.L.)
Margin = The - dif ference be tween the safe ty limit and . the trip setpoint le s s the II. The margin is a param-eter used to account- for unknown or inaccurately computed parameter accuracies.
+
-_ = de termined by conservative direction of safaty limit' Span = Span of instrument channel Computation of Allowable Value (AV)
AV = Trip Setpoint + [(RD + 0.5 x Margin) x Span]
- . Error .. values stated in terms of perce nt of span (unless indicated otherwise)
- Square root of the som of the squares is a standard acceptable means for combining errors (see Reference 1)
REFERENCES:
- 1. ISA-567.04, - dated September, 1981, "Setpoints for Nuc le ar Safety-Related' Instrumentation Used in Nuclear Power Plants"
- 2. Scientific Apparatus Manu f acturers Association (SAMA),
S tandard PMC 20.1-1973, " Process Measurement and Control Terminology"
- 3. Regulatory Guide 1.105, Rev. 1, dated November 1976,
" Instrument Setpoints"
r; (4) The margin in the ' trip setpoint - (the '~dif ference between the . Safety
~
~ Analysis Limit and the~ Nominal Trip Setpoint less the combined channel error allowance) is a parameter used to account : for unknown or inaccu-rately . computed parameter accuracies. The minimum value of margin used was 0.35% of span.
.